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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Report: New York state adding 1 GW of nuclear to fleet
New York Gov. Kathy Hochul has instructed the state’s public electric utility to add at least 1 gigawatt of new nuclear by building a large-scale nuclear plant or a collection of smaller modular reactors, according to the Wall Street Journal.
David Weitzel, Youho Lee (Univ of New Mexico), Michael Short (MIT), Michael Laufer (Kairos Power), Sam Sham (ANL)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1176-1182
Much progress has recently been made on Molten Salt Reactor (MSR) technology with the strategic support of the Department of Energy (DOE). However, concerns regarding the structural material’s compatibility with the salt have hampered the detailed design and evaluation of reliability and economics. Existing research also neglects fluid flow when measuring alloy dissolution. FLiBe flow affects species diffusion through the salt and in turn modifies the reaction kinetics at the alloy surface. Without a proper understanding of the flow effects on alloy dissolution, MSR performance assessments will inevitably remain imprecise.
This research entails the construction of a subscale molten salt loop to test the effects of FLiBe flow on the corrosion rate of various alloys. Our test loop will consist of a molten salt pump connected to a bimetallic composite test loop with a sample holder for the tested alloys. The salt temperature and velocity can be varied independently to replicate the varied operating conditions in the MSR and better characterize the effects of FLiBe flow on corrosion. Investigating the effects of salt flow on alloy element dissolution will advance material choice for key reactor components. These findings will enable nuclear engineers to create more detailed and accurate plant designs.